ML19338F129

RO 80-071/01P-0:on 800925,during Surveillance Test to Verify Equipment Operating Times,Control Room Isolation Times Determined Contrary to Tech Spec.Caused by Tech Spec Error in Required Time Determination

ML19338F129
Person / Time
Site:	Beaver Valley
Issue date:	09/29/1980
From:	Werling J DUQUESNE LIGHT CO.
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
BVPS:JAW:987, RO-80-071-01P, RO-80-71-1P, NUDOCS 8010070552
Download: ML19338F129 (2)

Text

_ _ . _ _ _

.')*

3

'Af 912)4ss4ooo

==

' Sm DUQUESNE' LIGHT COMPANY Beaver Valley Power Station Post Office Box 4 Shippingport, PA 15077 September 29, 1980 BVPS: JAW:987 Beaver Valley Power Station, Unit No. 1  !

Docket No. 50-334, License No. DPR-66 l LER 80-071/01P l

Mr. B. H. Grier, Director Of Regulation  !

l United States Nuclear Regulatory Commission Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Grier:

In accordance with Technical Specification 6.9.1.8.1, Administrative Cottrols, the following occurrence is reported. This occurrence was reported to Mr. D. A. Beckman, the Beaver Valley NRC Resident Inspector, at 1345 hours0.0156 days <br />0.374 hours <br />0.00222 weeks <br />5.117725e-4 months <br /> on September 26, 1980.

During performance of the surveillance test to verify' Engineered Safety Features (ESF) equipment operating times, it was determined that the control room isolation times are not in accordance with the Technical Specification required response time of thirty (30) seconds considering a loss of offsite l power. Previous review had, it is felt, assumed the diesel start time of ten (10) seconds, but had failed to include diesel sequencing time. It has been determined the required time in the Technical Specifications is in error and l should have originally been specified as seventy-seven (77) seconds since the power supply for the control room isolation valves is energized at the forty (40) second sequence step on the diesel load sequencer. A request will be made to the NRR to revise the specified response time in the Technical Specifications from thirty (30) seconds to seventy-seven (77) seconds.

Wc hp 1

'W 0 070 5 6 2., 3 1

Mr. B. H. Grier September 29, 1980 BVPS: JAW:987 Page 2 For the control room isolation to be actuated and protect the operators from a hostile atmosphere, a CIB and BLACK 0UT signal must have been automatically initiated. It is believed that there will be enough of a time lag such that the operator could credibly deal with the mitigation of an accident and no adverse atmosphere could exist.

Very truly yours, 9

J. A. Werling I Superintendent ec: Director Of Management & Program Analysis United States Nuclear Regulatory Commission Washington, D. C. 20555 W. J. Ross, BVPS Licensing Project Manager United States Nuclear Regulatory Commission Washington, D. C. 20555 D. A. Beckman, Nuclear Regulatory Commission, BVPS Site Inspector P. Higgins, Secretary, Prime Movers Committee - EEI Nuclear Safety Analysis Center, Palo Alto, California Mr. John Alford, PA Public Utilities Commission, Harrisburg, PA i

U.S. NUCLEAR REOULATORY COMMISSION r NRC,.n ,FORM 366 V -

LICENSEE EVENT REPORT

[

CONTROL BLOCK: l 1

l l l l 1 lh 6

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION, Rl 7 8 9 l 1 l LICENSEE CODE l l l I4 5 l l l l l 1 LICENSE NuM8ER l l l l l@l26 25 I l l LICENSE TYPE JO l l@l57 CAT l

68 1@

CON'T l,0,_L, ]

7 8

$$7"CII 60 l@lOif 0101 61 i 0 1311I kl fi 01 o19l2. IGl@l TI o I ol 917_.lM@

DOCKET NUM8ER 68 69 EVENT DATE 74 75 REPORT DATE 80 1

EVENT DESCRIPTION AND PAOBABLE CONSEQUENCES h 10121l $66 Z nP_ l l

I'5'TTI l 1 10141I l lo isi i l 101611 l 10171 l l I O ls l ! I DE CODE SU8C E COMPONENT CODE SU8 CODE SU E 10191 7 8 9 I I IU l @ l,_l@ l_,,,j @ l 11 12 13 l 1 l l l l@ l l@ l20 l@

18 19

,,,, SEOUENTIAL OCCURRENCE REPORT REVISION LER RO EVSNT YE4R REPO TNO CODE . DE NO.

qj  ! -l  ! l / l~

_ 21 22 23 24 26 27 3 29 Jo 31 32 K N AC ON ON PLANT ME HOURS SB 1 FOR b 8. SUPPLI R MANUFACTURER I

J3 l@l34 l@ L_J@

35 I

36 l@ l 31 i I I 40 I

L_J@

di l

42 l@ l 43 l@ l 44 I I I 47 l@

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h 11 101 l I li t il 1 J ITTTII I mI i 11 14 1I l 7 8 9 80 SA S 4 POWER OTHER STATUS IS O RY DISCOVERY DESCRIPTION I i i s 1 [_.J@ l i I l@l i I l@L_ l ACTivlTY CO TENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE 7

1 6 I 8 9 lhl to l l 11 44 l l 45 80 l

PERSONNEL EX?OSURES .

NUV8ER DESCRIPTION ITTT1 I I I l@lTYPE l @l I PERSONNE L INJU IES NUM8ER OESCRIPTION li la l l l l l@l12 l 7 8 9 11 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION i 9 L_J@l10 I 7 8 9 80 2 O ISSUET@DE i l CRIPTION i i i iiiiiiiiiili 7 8 9 10 68 6A 80 %

NAME OF PREPARER PHONE: